ML20038B351
| ML20038B351 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/10/1981 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20038B348 | List: |
| References | |
| NUDOCS 8112080053 | |
| Download: ML20038B351 (3) | |
Text
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7590-01 UNITED STATES '0F'A!! ERICA NUCLEAR REGULATORY C0!C11SSION In the 11atter of
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BOST0'l EDISON C0!!PANY
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(Pilgrim Nuclear Power Station,
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Docket No. 50-293 Unit 1)
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EXE!!PTION I.
The Boston Edison Company (licensee) is the holder of Facility Operating License No. DPR-35 which authorizes the operation of the Pilgrim Nuclear Power Station, Unit 1, at steady state reactor power levels not in excess of 1998 megawatts thermal (rated power). This license provides, among other thi6gs m that it is subject to all rules, regulations and orders of the Commission now or
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hereafter in effect. -The facility consists of a boiling water reactor. located at the licensee's site near Plymouth, Massachusetts.
II.-
Section III.G.3 of Appendix R to 10 CFR Part 50 requires that a fixed fire suppression system be installed in an area, room or zone under consideration for alternative safe shutdown modifications.
In the case of Pilgrim I, under this provision a fire suppression system would be required in the Control' Room.
The licensee indicated that the fire protection features currently installed together with constant availability of plant personnel assure that any fire would be detected and controlled immediately (BECO 81-59, March 18,1981).
Therefore, the licensee requested an exemption from the requirement to install
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a fixed fire suppression system in the Control Room.
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1 The licensee's exemption request was based on the following-
- The plant can be brought to a safe shutdown using the alternate shutdown system designed and installed for the Cable Spreading Room. The licensee has a detailed procedure to safely shut down the plant in the event the Control Room becomes uninhabitable.
Smoke detection is provided in some panels.
s A water hose station is installed in the corridor outside the main entrance to the Control Room.
The licensee has also confirmed that:
Portable fire extinguishers are provided in the Control Room.
The Control Room is separated from high risk areas by 3-hour fire rated barriers.
The modifications which the licensee's exemption request is based on are required by Appendix R to 10 CFR Part 50. Therefore, the above modifications alone do not justify an exemption from the requirement to install a fixed fire suppression system in areas where redundant divisions are located.
However, the~ Control Room is a unique area of the plant that is required to be continually occupied by the operators.
In the event of a fire, manual fire suppression would be effective and prompt.
Because the operators provide a continuous fire watch in the' Control Room, a fixed suppression system is not necessary to achieve adequate fire protection in the Control Room.
This is similar to the concept reflected in the staff's acceptance, on a short-term basis, of a continuous fire watch as an alternative to fixed suppression systens when such systems become unavailable per 3.7.11.2 of the l
Standard Technical Specifications.
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Based on our evaluation, we conclude that the licensee's installed fire protection for the Control Room meets the objectives of Section III.G " Fire Protection of Safe Shutdown Capability" of Appendix R to 10 CFR Part 50, and, therefore, the licensee's request to be exempted from the requirement to provide a fixed fire suppression system in the Control Room should be granted.
III.
Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12, an exemption is authorized by. law and will not endanger life or property or the common defense and security and is otherwise in the public interest.
.The NRC staff has determined that the granting of this exemption will not result in any significant environmental impact and-that pursuant to 10 CFR 51.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with this action.
l FOR THE NUCLEAR REGULATORY COMMISSION l
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Harold R. Denton, Director Office of Nuclear Reactor Regulation I
l Dated at Bethesda, Maryland this 10th day of November 1981 l
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